IEEE 603-2018 pdf free download – IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
NOTE—Asafety function is achieved by the completion of all required protective acbons by the reactor tic system or the enneered safety featses coricurent with the completion of all rsed actions by the aux*avy supportwig features, or both. (SeeAnr.ex Afor an illustrative exampIe)
safetygroup:Agiven ran ral set of interconnected components, modules, and equipment that can accomplish a safety function.
NOTE—Asatety group indudes one or more cbvlsions. (SeeAnnex Abc an illustrative examplej
safety system: A system that is raked upon to remien functional during and following design basis events to assure one of the blowing:
a) The integrity of the reactor coolant pressure boundary
b) The capability to shut down the reactor and maintain it na safe shutdown condition
c) The capability to prevent or mitigate the consequences of accidents that could result in potential off site exposures comparable to regulatory guidelines
sense aid command featixes: The electrical and mechanical components and interconnections involved in generating those signals associated directly or indirectly with the safety functions. The scope of the sense and command features extends from the measured process variables to the execute features’input terminals.
sensor: The portion of a channel that responds to changes in a plant variable or condition and converts the measured process variable into a signal suitable for use in the remainder of the
channel.
4. Safety system design basis
A specific basis shall be established for the design of each safety system of the nuclear power generating station. The design basis shall also be available as needed to facditate the determination of the adequacy of the safety system. including design changes. The design basis shall document as a minimum:
a) All design basis events plicable to each mode of operation of the generating station along with the initial conditions and analytical limits of plant conditions for each such event.
b) The safety functions and corresponding protective actions of the execute features for each design basis event.
c) The pemiissive conditions for each operating bypass capability that is to be provided.
d) The variables that are monitored to control each protective action. For each. idenbfy the associated:
1) Analytical limit
2) Range (normal. abnormal, and accident conditions).
3) Rate of change to be accommodated until coriwletion of the protective action.
a) The protective actions identified in item b) that may be controlled by manual means initially or subsequently to initiation. For each manual protective action, identify the folowing:
1) The points in time and the plant conditions dising which manual control is allowed.
2) The justification for permitting initiation or control subsequent to initiation solely by manual means.
3) The range of environmental conditions imposed upon the operator during normal, abnormal, and accident conditions throughout which the manual operations shall be performed.
4) The variables in item d) that shall be chsplayed for the operator to use in taking manual action. See IEEE Std 497 for additional information.IEEE 603 pdf download.